PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING SEPTEMBER, 1960

Technical Report · Sat Oct 01 04:00:00 EDT 1960

DOI:https://doi.org/10.2172/4086627· OSTI ID:4086627

Dayton, R. W.; Tipton, Jr., C. R.

The study of possible reactions induced by the application of high pressures at high temperatures was concentrated on U/sub 3/O/sub 8/-Al/sub 2/O/ sub 3/. Data are reported on the effects of temperature on the tensile properties of fully recryatallized Cr-- Hb, Nb-- V, Nb-- Zr, and Cr-- Nb-- Zr alloys. The effect of radiation on the creep properties of Zircaloy-2 at elevated temperatures is being studied. Magnesium oxides are being evaluated as a fuel matrix material for uranium dioxide. Specimens of niobium-base birary alloys containing 10, 20, and 30 wt.% uranium and ternary alloys containing 20 wt.% uranium with 10 or 20 wt.% Zr were prepared with enriched uranium for irradiation tests. Pu--Nb, Pu-- Th, Mo-- Pu-- U, and Nb-- Pu--U alloys were selected as candidates in the search for improved irradiation resistance. Specimens consisting of uranium nitride dispersed in C, Cr, Fe, Mo, Nb, Ta, Ti, W, and Zr were fabricated and heat-treated to evaluate compatibility. A summary of results is presented from 3 hr, 1430 deg C, 5 tsi hydrostatic pressings of various types of uranium carbide and U--C -Nb systems. The effects of heat- treatment on some properties of U-C syatems are presented. Data are presented on the corrosion resistance of UC -Mo/sub 2/C, UC --NbC, UC -TiC, UC --VC, Uc -- ZrC --Mo/sub 2/C, and UC -- ZrC --VC to Santowax R at 350 C for7 days. The development of powder metallurgy and melting and casting techniques for uranium nitrides is reported. Creep and atress-rupture tests are reported on Zircaloy-2 sheet specimens. Fission gas release experiments are reported on fueled-graphite spheres in suppent of the Pebble-bed Reactor. In the development of container materials for LAMPRE applications, the fabrication behavior of 13 birary tantalum- base alloys was investigated. Radiation-effects studies of fuel specimens of UO/ sub 2/ dispersed in BeO and Al/sub 2/O/sub 3/ and UC and UC/sub 2/ dispersed in graphite are reported. Studies are being conducted to develop an instrumented fuel plate for irradiation in the SM-1 and to develop fuel, absorber, and suppressor materials for the SM-2. A process is being investigated for the fabrication of dense BeO--UC/sub 2/ fuel pellets by cold pressing and sintering. A program to study the effects of irradiation on Hastelloy-X-clad compacts of highly enriched UC/sub 2/ is in progress. Thorium samples were nickel plated for corrosion testing under atmospheric conditions and in watersaturated air at 120 and 200 deg F. Data are reported on the corrosion of thorium, uranium, and U--10 wt.% Mo alloy under three types of conditions. (For preceding period see BMI- 1464.) (W.L.H.)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• NSA Number: NSA-15-011448
• OSTI ID: 4086627
• Report Number(s): BMI-1469
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ABSORPTION
AIR
ALUMINUM OXIDES
BERYLLIUM OXIDES
CARBON
CASTING
CHROMIUM
CHROMIUM ALLOYS
CORROSION
CREEP
DISPERSIONS
ELECTRODEPOSITION
ENRICHMENT
FISSION PRODUCTS
FUEL CANS
GASES
GRAPHITE
HEAT TREATMENTS
HIGH TEMPERATURE
IRON
IRRADIATION
MAGNESIUM OXIDES
MATERIALS TESTING
MELTING
METALLURGY
METALS, CERAMICS, AND OTHER MATERIALS
MOLYBDENUM
MOLYBDENUM ALLOYS
MOLYBDENUM CARBIDES
NICKEL
NIOBIUM
NIOBIUM ALLOYS
NIOBIUM CARBIDES
NITRIDES
PEBBLE BED
PLUTONIUM ALLOYS
POWDERS
PRESSURE
SINTERING
SPHERES
STRESSES
TANTALUM
TANTALUM ALLOYS
TENSILE PROPERTIES
THORIUM
TITANIUM
TITANIUM CARBIDES
TUNGSTEN
U3O8
URANIUM
URANIUM ALLOYS
URANIUM CARBIDES